REACTOR KINETICS WITH THE GROUP DIFFUSION MODEL
Technical Report
·
OSTI ID:4246595
A procedure is described for combining the calculation of time-dependent neutron fluxes with thermal analysis. A rather simple forward integration technique used for near critical systems is modified by timedependent perturbation theory for more reactive systems. A method for calculating flux and adjoint eigenvectors and eigenvalues is described. Spatial flux distributions are based on a generalization of the flux synthesis technique. (auth)
- Research Organization:
- Knolls Atomic Power Lab., Schenectady, N.Y.
- DOE Contract Number:
- W-31-109-ENG-52
- NSA Number:
- NSA-13-017057
- OSTI ID:
- 4246595
- Report Number(s):
- KAPL-M-ELW-8
- Country of Publication:
- United States
- Language:
- English
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